19results about How to "Reduce Radiation Risk" patented technology

The invention discloses a sacroiliac joint synthetic CT examination technology and system, and belongs to the technical field of medical image processing, and the technology comprises the steps: data input: employing an MRI image of an axial 3DT1 MGE sequence as input data, and guaranteeing that the image quality meets the subsequent processing requirements; in the deep learning model, a deep learning neural network model is designed and trained, the model can automatically learn the mapping relation between the MRI image and the CT image, and the MRI image is converted into a CT-like image with similar CT characteristics; image processing and optimization: through image enhancement, denoising and edge detection algorithms, the quality of the generated CT-like image is further optimized, and it is ensured that the CT-like image has high resolution and accuracy when displaying erosion, hardening and ankylosing lesions. The sacroiliac joint synthetic CT examination technology and the system thereof are a promising imaging evaluation method, the advantages of MRI and CT are combined, the diagnosis accuracy of sacroiliac joint lesions is improved, and meanwhile the risk that a patient receives radiation is reduced.

The present invention discloses a pneumatic sample transport device based on deceleration and positioning, the device consists of a positioning component and a deceleration component; the positioning component comprises a U-shaped rabbit pipe with an opening downward and one end as a starting end and the other end as a destination end, and a sample transport device arranged in the U-shaped rabbit pipe and transporting target materials from one end to the other end; the U-shaped rabbit pipe and the sample transport device are respectively provided with magnets that attract each other, the deceleration component comprises a ventilation component arranged at the starting end of the U-shaped rabbit pipe, a deceleration component arranged at the destination end of the U-shaped rabbit pipe, and a plurality of sensor components arranged in the bend of the U-shaped rabbit pipe. The present invention decelerates the sample transport device through a control system and positions the sample transport device through the principle of magnetic attraction, thereby avoiding damage to the sample transport device and the contained sample due to severe impact, and improving automation and reducing the difficulty of manipulator design through automatic positioning of the sample transport device.

The invention relates to the technical field of medical isotope production, in particular to a solid target piece disassembling device and method. The disassembling device comprises a pushing assembly, a first cutting assembly and a second cutting assembly. The pushing assembly comprises a transverse moving module, a tray and a moving frame, the tray and the moving frame are both installed on the transverse moving module, a groove is formed in the moving frame, and the tray is located on the lower side of the groove; the first cutting assembly comprises a support, a longitudinal moving module and a flywheel, the support is located on the upper side of the pushing assembly, a containing groove for installing a target piece is formed in the support, the longitudinal moving module is installed on the support and is perpendicular to the transverse moving module, and the flywheel is installed on the longitudinal moving module; the second cutting assembly comprises a driving mechanism and a cutting piece, the driving mechanism is located at the tail end of the transverse moving module, and the cutting piece is installed on the bottom side of the driving mechanism. The problems that in the prior art, the safety risk is high, the efficiency is low, disassembling is difficult, and the integrity of the target material is difficult to guarantee are solved.

The utility model relates to the field of nondestructive testing, and discloses a pipeline detection device, which comprises a mounting ring, a shielding assembly and a supporting assembly, and is characterized in that the mounting ring is used for sleeving a to-be-detected pipeline; the shielding assembly is mounted on the mounting ring and is used for fixing the radioactive source, and the shielding assembly is further used for allowing rays emitted by the radioactive source to be emitted in the transillumination direction and inhibiting the rays emitted by the radioactive source from being emitted in the non-transillumination direction; the transillumination direction is the direction from the shielding assembly to the cassette; the support assembly is mounted on the mounting ring, and the support assembly is configured to mount the cassette. Therefore, the rays emitted by the radioactive source can be conveniently utilized to carry out nondestructive detection on the pipeline, the environmental dose of a radioactive source detection place is reduced, the radiation risk of radioactive source detection is reduced, the isolation boundary range of radioactive source detection is narrowed, and the radioactive source detection cost is reduced.

The nondestructive detection vehicle comprises a vehicle base, four driving motors and a first electric telescopic cylinder are installed on the vehicle base, a Mecanum wheel is installed on a power output shaft of each driving motor, a lifting motion support is installed at the top end of the first electric telescopic cylinder, and the lifting motion support and the first electric telescopic cylinder are installed on the vehicle base. A second electric telescopic cylinder and an overturning support are hinged to the lifting motion support, the tail end of a piston rod of the second electric telescopic cylinder is hinged to the overturning support, a third electric telescopic cylinder and a ray emitter are installed on the overturning support, and a detector support is installed at the tail end of a piston rod of the third electric telescopic cylinder. And an X-ray flat panel detector is mounted on the detector bracket. The device has the beneficial effects that the ray emitter and the X-ray flat panel detector are supported, carried and subjected to angle adjustment, the labor intensity of detection personnel is reduced, the device can be remotely operated by the detection personnel, and the radiation risk to the detection personnel is reduced.

The utility model discloses a nuclear power station water quality purifying and filtering integrated device which comprises an airtight container, a water inlet, a water outlet, a charging port and a discharging port, and the interior of the airtight container is divided into an upper-layer compartment, a middle-layer compartment and a lower-layer compartment from top to bottom through at least two partition plates. The upper-layer compartment, the middle-layer compartment and the lower-layer compartment are sequentially communicated through a plurality of water distributors arranged on the partition plate, and the middle-layer compartment is filled with ion exchange resin; the water inlet is communicated with the upper-layer compartment for water inflow, and the water outlet is communicated with the lower-layer compartment for water outflow; the charging hole is communicated with the upper part of the middle-layer compartment and is used for charging the ion exchange resin, and the discharging hole is communicated with the lower part of the middle-layer compartment and is used for discharging the ion exchange resin. The water quality purification and filtration integrated device for the nuclear power station is integrated equipment, occupies less space, is simple in pipeline, and can be used for remotely replacing the ion exchange resin and reducing the radiation risk.

The invention relates to the field of performance inspection after material irradiation, in particular to a radioactive sample weighing device which comprises a shielding box. A balance; the shielding box is arranged in the shielding box; the sample bottle placing seat is arranged in the shielding box and is used for placing a sample bottle to be weighed; the mechanical arm is arranged in the shielding box, a clamping device is arranged at the action tail end of the mechanical arm, and the mechanical arm is used for clamping the sample bottle in the sample bottle placing seat based on the clamping device and moving the sample bottle to a balance so as to weigh the mass of a radioactive sample object in the sample bottle. According to the radioactive sample weighing device, radioactive samples can be accurately weighed, and the operation of workers and the irradiation dose can be reduced.

The invention relates to a rotary table device convenient for long-distance disassembly and assembly, which comprises a rotary fixed base, a rotary support transition plate, a rotary support, a rotary large disc, a positioning pin, a C-shaped fixed clamp and an electric wrench, and the top of the rotary fixed base is provided with an upper boss and a positioning key slot which are in positioning fit with the rotary support transition plate; a positioning pin hole for positioning the slewing bearing transition plate is also formed in the slewing fixing base; the rotary fixed base is fixed on the ground through foundation bolts, and has the advantages of few fault points, stable operation, high intelligent degree and the like.

The utility model relates to the technical field of robots used in nuclear power plants, in particular to an installation mechanism and an irradiation-resistant robot foreign matter prevention device. The sliding assembly comprises a containing part and a containing part. The locking assembly comprises a blocking piece, an operating piece and a rotating piece, the surrounding assembly comprises a surrounding piece and a mounting piece, the mounting piece is arranged on the blocking piece and the surrounding piece, the sliding assembly and the locking assembly act on the machine body, falling parts can be stored at the bottom of the robot, and under cooperation of the surrounding assembly, the falling parts can be stored in the bottom of the robot. According to the device, components on the two sides can be prevented from being separated in the working process of the whole robot, the whole device can well surround the robot, the foreign matter prevention effect of the robot is improved, the situation that the use efficiency of the robot is affected due to component falling is avoided, and therefore the working intensity of radiation protection workers and decontamination workers is greatly relieved; the dosage level of occupational irradiation received by the people is also remarkably reduced, and the radiation risk is further reduced.

The present application relates to the technical field of medical isotope production, and particularly relates to a solid target disassembling device and method. The disassembling device comprises a pushing assembly, a first cutting assembly and a second cutting assembly. The pushing assembly comprises a horizontal moving module, a tray and a moving frame. The tray and the moving frame are both installed on the horizontal moving module. A groove is formed on the moving frame, and the tray is located on the lower side of the groove. The first cutting assembly comprises a support, a vertical moving module and a flywheel. The support is located on the upper side of the pushing assembly. A placing groove for installing the target is formed on the support. The vertical moving module is installed on the support and is perpendicular to the horizontal moving module. The flywheel is installed on the vertical moving module. The second cutting assembly comprises a driving mechanism and a cutting piece. The driving mechanism is located at the end of the horizontal moving module. The cutting piece is installed on the bottom side of the driving mechanism. The present application solves the problems of high safety risk, low efficiency, difficult disassembly and difficulty in ensuring the integrity of the target material in the prior art.

The invention discloses a radiology department digital gastrointestinal machine imaging control method and system, and relates to the technical field of radiology department digital gastrointestinal machine imaging control, and the method comprises the steps: carrying out the data collection based on image collection and processing; carrying out image optimization and personalized dose control; and generating a report according to the acquired image and the control result. According to the method, X-ray dose parameters are predicted and adjusted in real time based on a deep learning algorithm and data collected in real time, the radiation dose is controlled at the lowest level on the premise of ensuring that diagnosis requirements are met, noise and artifacts in images are effectively removed through the technologies of noise filtering, high-pass filtering, non-local mean denoising and the like, and the diagnosis accuracy is improved. According to the method, the definition and readability of the image are improved, the diagnosis report is automatically generated according to the collected image and the control result, the time of a doctor is saved, the diagnosis efficiency is improved, the report generation process is automated, the possibility of human errors is reduced, and the report reliability is improved.

A traffic control apparatus is provided. The device comprises gate equipment, a detector and a controller. The gate equipment is used for allowing pedestrians meeting preset conditions to enter and exit the radiation area; the detector is used for detecting the number of pedestrians entering and exiting the radiation area each time; the controller comprises a control board card, and the control board card is used for receiving a detection result of the detector so as to count the number of pedestrians in the radiation area; wherein the control board card is configured to be electrically connected with safety interlocking equipment in the radiation area, and the control board card is further used for enabling the safety interlocking equipment to be in a specific state for indicating beam emission when no one is in the radiation area. The invention further provides a traffic control method.

This invention discloses a membrane-borne self-driven storage and retrieval device for online monitoring of αβ radioactive aerosols, relating to the technical field of aerosol storage equipment. It includes a storage chamber and a combination tray mechanism. The storage chamber has retrieval and placement ports on its side wall. The combination tray mechanisms are stacked within the storage chamber, with adjacent combination tray mechanisms connected and fixed by support pillars. A rotating sleeve is installed on the bottom combination tray mechanism, driven by an externally mounted motor. This invention designs each layer of the combination tray mechanism as an integrated top and bottom tray structure, with storage ports one and two respectively. This allows a single layer to simultaneously and independently store new membrane boxes and recycled old membrane boxes, achieving "dual-purpose storage" and effectively doubling the effective storage capacity. Combined with the rotatable sleeve design, the multi-layer combination tray mechanism can be cyclically positioned, allowing the retrieval and placement ports to sequentially connect to the storage positions on each layer, further maximizing the utilization of vertical space.

The invention relates to the technical field of medical instruments, in particular to a bone focus removing and bone grafting surgical robot which comprises a mounting frame and a sliding adjusting assembly slidably arranged on the upper portion of the mounting frame. Wherein the interior of the mounting frame body is provided with a cavity, the upper part of the mounting frame body is provided with a moving groove, the moving groove is communicated with the cavity, one side of the mounting frame body is fixedly provided with a moving motor, and an output shaft of the moving motor is arranged in the cavity along the axial direction of the mounting frame body; the sliding adjusting assembly comprises a rotating base arranged in the moving groove in a sliding mode, a supporting arm rotationally arranged on the upper portion of the rotating base, and a first lifting device rotationally arranged on one side of the upper portion of the supporting arm. According to the method, frequent interruption caused by visual field cleaning, repositioning and the like in a traditional operation is not needed, the operation duration is greatly shortened, and a better, more efficient and safer solution is provided for a bone focus removing and bone grafting operation on the whole.

This invention relates to the technical field of radioactive waste treatment, and discloses a combined packaging container for radioactive waste in a hot chamber, a shielding system, and a method for shielding radioactive waste. The combined packaging container for radioactive waste in a hot chamber includes a transfer container, a sealing container, and a fixing mechanism. The transfer container has a gripping part on its periphery for a robotic arm to grip and empty the container. The sealing container includes a sealing cap and a sealing body. The sealing cap is closably connected to the sealing body, and the sealing body defines a sealing cavity for storing radioactive waste. The sealing cap has a first clamping position for connection to the robotic arm, and the sealing body has a second clamping position. The fixing mechanism has a clamping part and a movable part connected to each other. The clamping part is driven by the movable part to switch between a first position and a second position. The combined packaging container for radioactive waste in a hot chamber of this invention can improve the sealing performance of the sealing container and reduce the radiation risk of radioactive waste.

The utility model discloses a protective box for a strontium 90 application source. The protective box comprises a box body and a box cover, the box body is provided with a groove body for placing a strontium 90 application source, and the strontium 90 application source is placed in the groove body with a source window facing downwards; the strontium 90 application source is sealed in the box body by the box cover, and the protection box formed by the box cover and the box body is cylindrical and is used for being matched with a cylindrical source tank for use. The protection box for the strontium 90 application source is cylindrical and can be used in cooperation with an existing cylindrical source tank, the universality of the source tank is improved, and the cost for redesigning and purchasing the source tank is reduced; meanwhile, the design of the protection box can reduce the tough-induced radiation, protect the radioactive source, improve the operation portability and reduce the radiation dose of operators.

This invention relates to the field of ridge filter design technology, and discloses a design method, system, device, and storage medium for ridge filters. The method includes acquiring first and second actual water depth dose distribution data for proton and heavy ion beams with multiple energies; performing Monte Carlo simulation on the proton and heavy ion beams to obtain a Monte Carlo beam model; constructing a geometric optimization model for the ridge filter using its geometric parameters as optimization variables, maximizing its performance index as the objective function, and using geometric parameter constraints as constraints; and solving the geometric optimization model using a particle swarm optimization algorithm to obtain the optimal geometric parameters. This invention can improve the parameter design accuracy of ridge filters, reduce the processing accuracy requirements of ridge filters, improve the flatness of the effective biological dose in the extended Bragg peak, and reduce the radiation risk from secondary neutrons.

The invention discloses a target changing system and a control method, the target changing system is used for changing a target piece of a neutron target, and the target changing system comprises a three-coordinate mobile platform, a mechanical arm, an image acquisition device and a background processing terminal; a dismounting mechanism is mounted on the three-coordinate moving platform; a transfer assembly is arranged on the disassembly and assembly mechanism, the transfer assembly can be in adsorption connection with the target sheet, and an alignment piece is arranged on the disassembly and assembly mechanism and used for being aligned with a target position on the target sheet; an image acquisition device is also arranged on the dismounting mechanism and is used for acquiring an alignment piece image and transmitting the alignment piece image to a background processing terminal; the background processing terminal is used for processing according to the alignment piece image acquired by the image acquisition device to obtain a relative position deviation value between the alignment piece and a target position on the target piece, and further controlling the moving action of the three-coordinate moving platform and the dismounting action of the dismounting mechanism; the mechanical arm is arranged on the side of the three-coordinate moving platform and used for providing a new target piece for the disassembling and assembling mechanism or transferring an old target piece disassembled by the disassembling and assembling mechanism to a transfer final position.

The utility model provides a device for separating and purifying metal nuclides. The device comprises a base, a top cover and an outer cylinder positioned between the base and the top cover, wherein the top cover consists of an upper sleeve and a cooling container; the upper sleeve is of a hollow cylinder structure, the bottom of the upper sleeve is open, the top of the upper sleeve and the bottom of the cooling container are fixedly sealed, and the bottom of the upper sleeve is slightly higher than the upper surface of the base. The device disclosed by the utility model is simple in structure and convenient to operate, and can meet the requirement of sublimation separation of radionuclides; the device is small in size and can be put into a protection box, the whole purification process is operated in the protection box, and the radiation risk is reduced; metal steam obtained in the sublimation process is mainly condensed in the upper sleeve and can be conveniently dissolved with acid to be recycled and reused.